DCL-19-086, Supplement to License Amendment Request 18-02, License Amendment Request to Revise Technical Specification 5.6.5b, 'Core Operating Limits Report (Colr)' for Full Spectrum Loss-of-Coolant Accident Methodology

Supplement to License Amendment Request 18-02, License Amendment Request to Revise Technical Specification 5.6.5b, 'Core Operating Limits Report (Colr)' for Full Spectrum Loss-of-Coolant Accident Methodology

ML19297H634
Person / Time
Site:	Diablo Canyon
Issue date:	10/24/2019
From:	Gerfen P Pacific Gas & Electric Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
DCL-19-086
Download: ML19297H634 (2)

Text

Pacific Gas and Electric Company*

Paula Gerten Diablo Canyon Power Plant Site Vice President Mail code 104/6/605 P.O. Box 56 Avila Beach, CA 93424 805.545.4596 Internal: 691.4596 Fax: 805.545.4234 October 24, 2019 PG&E Letter DCL-19-086 U.S. Nuclear Regulatory Commission 10 CFR 50.90 ATTN: Document Control De~k Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 Supplement to "License Amendment Request 18-02, License Amendment Request to Revise Technical Specification 5.6.5b, 'Core Operating Limits Report (COLR)' for Full Spectrum Loss-of-Coolant Accident Methodology"

Reference:

1. PG&E Letter DCL-18-100, "License Amendment Request 18-02, License Amendment Request to Revise Technical Specification 5.6.5b, 'Core Operating Limits Report (COLR)' for Full Spectrum Loss-of-Coolant Accident Methodology," dated December 26, 2018 [ML19003A196]

Dear Commissioners and Staff:

In Reference 1, Pacific Gas and Electric Company (PG&E) submitted a license amendment request (LAR) to revise the Technical Specification 5.6.5b, "Core Operating Limits Report (COLR)" for the Westinghouse Full Spectrum TM Loss-of-Coolant Accident (FSLOCA') Methodology. Attachment 4 to the Enclosure of Reference 1 provided the Updated Final Safety Analysis Report (UFSAR) changes associated with the FSLOCATM analysis for information only.

During NRC staff review of the LAR (Reference 1), the staff identified an error in the UFSAR changes contained in Attachment 4. Specifically, in UFSAR Table 6.5-2, "Summary of Assumptions Auxiliary Feedwater [AFW] System Design Verification," line item e., "Decay Heat," column "Small Break Loss of Coolant Accident," the reference was revised from "Figure 15.1-7" to "Figure 15.1-6; however Figure 15.1-6, "Residual Decay Heat (Best Estimate LBLOCA 1979 ANS Decay Heat)" was marked as being deleted.

The decay heat curve used in the FSLOCATM analysis is described in to the Enclosure of Reference 1 in UFSAR Section 15.1.10.1 A member of the STARS Alliance Callaway

• Diablo Canyon

• Palo Verde

• Wolf Creek

Document Control Desk PG&E Letter DCL-19-086 October 24, 2019 Page 2 (UFSAR page 15.1-14), "Fission Product Decay." Therefore, the correct reference for UFSAR Table 6.5-2, line item e., "Decay Heat," column "Small Break Loss of Coolant Accident," is "Section 15.1.10.1."

The UFSAR change described in this supplement does not impact the significant hazards consideration evaluation, Technical Specifications changes, or the Technical Specification Bases changes contained in Reference 1.

PG&E makes no new or revised regulatory commitments (as defined by NEI 99-04) in this letter.

If you have any questions or require additional information, please contact Mr. Hossein Hamzehee, Regulatory Services Manager, at (805) 545-4720.

I state under penalty of perjury that the foregoing is true and correct.

Executed on October 24, 2019.

Sincen

//AJ~t;+

Paula Gerfen U Site Vice President kjse/4328/51049726 cc: Diablo Distribution Scott A. Morris, NRC Region IV Administrator Gonzalo L. Perez, Branch Chief, California Department of Public Health John P. Reynoso, Acting NRC Senior Resident Inspector Balwant K. Singal, NRC Senior Project Manager A member of the STARS Alliance Callaway

• Diablo Canyon

• Palo Verde

• Wolf Creek